Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission

Save this PDF as:
 WORD  PNG  TXT  JPG

Size: px
Start display at page:

Download "Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission"

Transcription

1 Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. Paz-Soldan 2, F. Carpanese 3, C.C. Petty 2, T.C. Luce 2 1 Columbia U. 2 General Atomics 3 Dipartimento di Energetica, Politecnico di Milano IAEA-TM, Roma, March 6 th 2015

2 Contents - Making progress by integrating modelling and experiment à MHD spectroscopy to measure the approach to a limit à The MARS-K model for plasma response calculations à The PEST3 model to evaluate Δ trends - The ITER Baseline Scenario: moderate β N, zero torque - The path to high β N and steady-state conditions à Modeling the no-wall limit crossing with non-ideal effects - The steady-state scenarios: high β N, high torque - Low torque at high β N - Discussion and conclusions

3 DIII-D studies demonstration plasmas relevant to these scenarios: ITER Baseline Scenario (IBS) (RWM studies) ITER Steady- State ITER I p (MA) 15 / 9 q Q 10 / 5 DIII-D β N DIII-D Torque (Nm)

4 DIII-D studies demonstration plasmas relevant to these scenarios: ITER Baseline Scenario (IBS) (RWM studies) ITER Steady- State ITER I p (MA) 15 / 9 q Q 10 / 5 DIII-D β N DIII-D Torque (Nm)

5 DIII-D studies demonstration plasmas relevant to these scenarios: ITER Baseline Scenario (IBS) (RWM studies) ITER Steady- State ITER I p (MA) 15 / 9 q Q 10 / 5 DIII-D β N DIII-D Torque (Nm)

6 DIII-D studies demonstration plasmas relevant to these scenarios: ITER Baseline Scenario (IBS) (RWM studies) ITER Steady- State ITER I p (MA) 15 / 9 q Q 10 / 5 DIII-D β N DIII-D Torque (Nm)

7 DIII-D studies demonstration plasmas relevant to these scenarios: ITER Baseline Scenario (IBS) (RWM studies) ITER Steady- State ITER I p (MA) 15 / 9 q Q 10 / 5 DIII-D β N DIII-D Torque (Nm) à Experiment à Modelling

8 Measure the approach to instability: MHD spectroscopy EXP MHD spectroscopy*: A rotating kink-resonant n=1 field is applied with a set of internal coils (I-coils), at f=10 Hz or f=20 Hz ß rotation frequency of the RWM à The plasma response amplitude increases close to a stability boundary à The phase shows a jump Used to probe the proximity to a stability limit Expand the analysis and modeling space to the stable side of the modes * Fasoli PRL1995 * Reimerdes PRL 2004

9 RWMs: slowly growing, slowly rotating kinks MOD The ideal kink instability, with a realistic (non-ideal) wall model, is described by the RWM branch of the dispersion relation à slow growth rate of the order of τ wall (~2.5 ms in DIII-D) The RWM is influenced by à pressure and current profile gradients (ideal MHD) à resonances between the plasma rotation and the thermal particles drift frequencies à non-resonant contributions from fast-particles (NBI ions in DIII-D) In DIII-D, RWMs Cause rotation and β N collapses in the high-q min, high-β N SS plasmas

10 Drift kinetic effects are needed to describe the experimental observations MOD RWMs do not usually appear in fast-rotating, low q min plasmas à kinetic damping of the RWM [Hu et al, PRL2004] γτ W = δw NW δw WW Ideal MHD RWM dispersion relation γτ W = δw NW +δw K δw WW +δw K Kinetic damping physics δw k ~ l ( ω ω E ) f ε n f ψ ez ω ω p ω b + iν eff ω E Precession frequency Bounce frequency Collision frequency Kinetic dependences may extrapolate unfavourably for low external torque and lower fraction of fast beam-generated ions (ITER) à need to validate models for rotation and thermal/fast particles

11 MARS-K model is being validated to predict the stability in unexplored regimes MOD Eigenvalue code, modified to solve for the response to an inhomogeneous forcing function ß External field from the I-coils The model includes - resistive DIII-D wall geometry - rotation, T e, T i, n e from experiment - fast-nbi ions with a Maxwellian slowing down distribution function - radially constant collisionality (for ions and electrons) *Y. Liu et al, Phys. Plasmas 15, (2008)

12 [IBS] MHD stability below the no-wall limit, at zero torque ITER Baseline Scenario (IBS) (RWM studies) ITER Steady- State ITER I p (MA) 15 / 9 q Q 10 / 5 DIII-D β N DIII-D Torque (Nm)

13 [IBS] Stable solution found at moderate to high torque EXP DIII-D IBS demonstration discharges match - plasma shape (LSN) - q 95 = Q = 10 ß β N =1.8, H 98 =1 at q 95 =3 DIII-D can match the predicted torque à Nm Solution non reproducible (50% of cases are unstable)

14 [IBS] At zero torque life is hard... EXP - Narrow operating point found at 1 Nm - Operation at 0 Nm remains elusive Operating on a marginal point à sensitive to small perturbations Ideal no-wall limit β NW ~ Ideal with-wall limit β WW ~ IBS constant β N ~ Non-ideal effects à current profile, rotation, collisionality, resistivity?

15 [IBS] MHD spectroscopy shows that the plasmas are approaching a stability limit EXP Response amplitude increase Non-ideal effects ß à Lower limits Phase jump at ~12-15 krad/s à Typical of no-wall limit crossing Response AMP (G/kA) Response PHI ( ) β N ~ β N ~ Phase jump NBI torque (Nm) NBI torque (Nm) Rotation at ρ~0.7 (krad/s)

16 [IBS] The plasma response trends indicate that non-ideal effects are present EXP - At moderate rotation, the trends are consistent with the ideal model Plasma response amplitude (G/kA) β N /β lim Rotation at ρ=0.7 (krad/s)

17 [IBS] The plasma response trends indicate that non-ideal effects are present EXP - At moderate rotation, the trends are consistent with the ideal model - At higher rotation the response is off trend à kinetic damping? Plasma response amplitude (G/kA) β N /β lim Rotation at ρ=0.7 (krad/s)

18 [IBS] The plasma response trends indicate that non-ideal effects are present EXP - At moderate rotation, the trends are consistent with the ideal model - At higher rotation the response is off trend à kinetic damping? - At very low rotation, with ECH, higher response à collisionality? resistivity? Ideal MHD likely not sufficient to explain the trends Plasma response amplitude (G/kA) β N /β lim Rotation at ρ=0.7 (krad/s)

19 [IBS] MARS-K reproduces only the higher rotation cases EXP - Collisionality is important to reproduce the higher rotation range correctly - MARS does not capture the large increase at very low rotation - The phase is overestimated by ~15-20 Response amplitude(g/ka) MARS-K w/o coll. MARS-K w/ coll. NBI torque (Nm) Response phase ( ) NBI torque (Nm) (B r ) Rotation at ρ~0.7 (krad/s)

20 The path to high β N is a good platform to validate models ITER Baseline Scenario (IBS) (RWM studies) ITER Steady- State ITER I p (MA) 15 / 9 q Q 10 / 5 DIII-D β N DIII-D Torque (Nm) Higher β N Higher q 95

21 Pressure (β N ) scan to cross the no-wall β N limit EXP Increase the pressure with co-ip NBI power à fixed q95, li à Measure the plasma response

22 β N scan: It s crucial to assess the validity of the modeling results MOD Rotation has an impact on the response amplitude The rotation is not constant across the β N values à Sensitivity study: assess impact of rotation on the results

23 β N scan: MHD-only model does not reproduce approach to the no-wall β N limit MOD Previous modelling* showed the MHD model without rotation has a pole at the no-wall limit *Lanctot, PoP2010 Plasma Response Amplitude (GkA) Plasma Response Phase ( ) Experiment MHD only Kinetic Ideal model Model No-wall limit (without rotation) No-wall limit (without rotation) β N

24 β N scan: Drift kinetic model reproduces approach to the no-wall β N limit correctly MOD Previous modelling* showed the MHD model without rotation has a pole at the no-wall limit The pole is eliminated with the full kinetic model (thermal + fast ions) *Lanctot, PoP2010 Plasma Response Amplitude (GkA) Plasma Response Phase ( ) Experiment MHD only Full kinetic Kinetic Model No-wall limit (without rotation) No-wall limit (without rotation) β N

25 β N scan: Drift kinetic model reproduces approach to the no-wall β N limit correctly MOD Previous modelling* showed the MHD model without rotation has a pole at the no-wall limit The pole is eliminated with the full kinetic model (thermal + fast ions) Without fast-ion damping the pole reappears à 45% higher than expt The phase shift is still overestimated above the no-wall limit ITER: very small fast-ion β from NBI à will the plasmas be (45%) more unstable? à Will the fast α-particles be enough to stabilize them? *Lanctot, PoP2010 Plasma Response Amplitude (GkA) Plasma Response Phase ( ) Kinetic Model Experiment MHD only Thermal+fast +45% Thermal No-wall limit (without rotation) ?? No-wall limit (without rotation) β N

26 β N scan: Precession and bounce drift frequencies are the main factors MOD The full model is necessary to reproduce the experiment

27 ITER Baseline Scenario (IBS) (RWM studies) ITER Steady- State ITER I p (MA) 15 / 9 q Q 10 / 5 DIII-D β N DIII-D Torque (Nm) Higher β N Higher Torque

28 [SS] MHD stability is the main challenge for high-β N scenarios EXP - High rotation, β N <=3.6 à can be made passively stable - 2/1 tearing modes arise on β N >3.6 flattop - They degrade the confinement significantly à loss of 20-50% β N β N I p n=1 amplitude (G) , , Time (ms)

29 [SS] Tearing limits are strongly correlated with the ideal with-wall limit MOD The tearing index Δ increases sharply at the ideal wall limit Modelling of the approach to the ideal limit:

30 [SS] Tearing limits are strongly correlated with the ideal with-wall limit MOD The tearing index Δ increases sharply at the ideal wall limit High β N operation Operate with very large, very sensitive Δ? Modelling of the approach to the ideal limit: One solution is to increase the ideal limit: - broaden J and p - change the plasma shape Turnbull, PRL 1995 Turnbull, NF 1998

31 [SS] OFF-axis NBI used to broaden the pressure and current profiles The with-wall β N limits of the OFF-axis cases are ~10% higher

32 [SS] Shape modifications can yield β limit ~6 MOD The with-wall β N limits of the OFF-axis cases are ~10% higher Combined changes of outer gap and squareness: β lim 4.5 à 6 With-wall β N limit Upper squareness

33 [SS] The PEST3 model captures the approach to tearing instability PEST3 Δ Time series of Δ calculated* for experimental equilibria β N ~4 Higher β N >4 cases à Δ shows increasing trend towards the 2/1 mode β N ~ Time (s)

34 [SS] For stable plasmas, Δ decreases The stable cases can have high Δ values But show a stable or decreasing trend on the flattop β N ~

35 [Rotation scan] All the high-β N plasmas have high NBI torque MOD What happens at low rotation, high β N? - Experiment à decrease the rotation at fixed β N, q 95 - Model à capture the rotation effects? fixed equilibrium and n e, T e, n i, P NBI, etc, from a DIII-D plasma a self-similar rotation profile series Plasma rotation and drift frequencies Plasma rotation (krad/s)

36 Rotation effects above the no-wall β N limit EXP Broad peak in the response at krad/s (~1% of the Alfvén velocity) Below the no-wall limit (IBS) the trend is increasing Response AMP (G/kA) MHD spectroscopy Response PHI ( ) Rotation at ρ~0.6 (krad/s)

37 [Rotation scan] MARS-K reproduces the response amplitude with fast-ions MOD MHD spectroscopy With thermal and fast ions, trend and amplitude are well matched...but the phase is underestimated by ~25% If the fast-ions damping is neglected, the results diverge (more) from the measurements Fast-ions destabilizing at high-β N? consistent with β N scan results... Response AMP (G/kA) Response PHI ( ) MARS-K w/ fast ions MARS-K w/o fast ions Rotation at ρ~0.6 (krad/s)

38 Summary and conclusions Modelling the approach to instability: how are we doing? - ITER Baseline Scenario: - Good match at moderate rotation - MARS-K does not reproduce the high response at zero torque - No-wall limit crossing: - MARS-K reproduces very well the response amplitude - The phase is overestimated at high β N - Steady-state scenarios: - PEST3 captures the approach to instability - No rotation dependence! Needed to extrapolate - The rotation dependence at high β N : - MARS-K captures the amplitude trends - The phase trends are not reproduced as well

39 What physics can be added and may be relevant? Collisionality à New MARS-Q: energy dependent collisionality operator Finite ion orbits? The present version of MARS-K assumes a Maxwellian fast-ion distribution (experimental profile in ρ, but no v //, v perp dependence) à Neutral beam ions in DIII-D are strongly anisotropic Large response at zero torque remains a puzzle... Experimental beam-ion distribution (NUBEAM)

40 EXTRAS

41 Current-driven mode: The mode structure is similar to that of the pressure-driven mode The mode eigenfunction is a combination of the main harmonics m=2,3,4,5 The structure of the mode extends radially inward à not only at the edge Comparable to the pressure-driven mode Previously developed RWM feedback techniques and the low q optimizations can be applied to both current-driven and pressure-driven, high β N modes F. Turco/IAEA 2014/St. Petersburg

42 MISK results for rotation scan

43 [IBS] MARS-K reproduces only the higher rotation cases EXP - Collisionality is important to reproduce the higher rotation range correctly - MARS does not capture the large increase at very low rotation - The phase is overestimated by ~15-20 Response amplitude(g/ka) MARS-K w/o coll. MARS-K w/ coll. NBI torque (Nm) Response phase ( ) (B p ) Rotation at ρ~0.7 (krad/s) NBI torque (Nm)

44 [IBS] MARS-K reproduces only the higher rotation cases EXP

45 The Hybrid Regime Addresses the Steady-State Challenges With An Alternative Approach What is a hybrid? à Long duration, high confinement H-mode à More stable to 2/1 tearing modes Final J independent from sources Current density All external current driven in the plasma centre SS High-q min SS Hybrid No alignment issues Most efficient CD q relaxes to hybrid state q min 1 q 3/2 TM q=1 q= , Ideal MHD with-wall limits are β limit 4.5 High q min present limits β lim ~ à predicted β lim ~5

46 The Highest β N Cases Are Limited By MHD At β N 3.6 à 2/1 tearing modes are avoidable At β N 4 à fishbone-like bursts, then 2/1 tearing modes à non-recoverable isolated bursts: β N , τ 1 ms, f khz n=1 Amp (G) τ 50 ms, f~10-15 khz The activity does not decrease with density à not fishbones? May be due to the large fraction of fast particles B dot B dot bursts Time (ms)

47 Hybrid plasmas reach fully NI conditions and β N =3.6 for ~2 τ R EXP Double null plasma shape β N τ R H98y , , P NBI (MW) P ECH (MW) Density (10 19 m -3 ) Stable to the 2/1 TM at β N ~3.6 Loop voltage ~ 0 for ~2 τ R Limited by NBI pulse duration V surf (mv) Time (ms)

48 The Scenario Is Sustained At High Injected Torque Lower Torque Degrades Confinement - 1 neutral beam line added in counter-i p direction (~4 MW) - Same β N, stored energy obtained Confinement decreases by ~20% for 35% lower T P NBI = 11 à 15 MW (35% increase) β N , P NBI (MW) 2/1 TM P ECH (MW) T NBI = 8.8 à 5.6 Nm (35% decrease) NBI torque (Nm) H 98y2 H 98y2 = 1.72 à 1.4 (20% decrease) Time (ms) 2/1 TM

49 With Present Confinement And n e, The DN Hybrid Is Consistent With an FNSF 6.7 MA Scenario INPUTS: R=2.49 m, B t = 6 T q 95 =6.2, ε=3.5 β N =3.66, n lin.av =4 DN 6.7 MA FNSF hybrid Plasma current (MA) scaled Impose I p = 6.7 MA Fix ν* H 98y2 =1.42 SCALED SCENARIO: With n/n G = 0.42 Drive 3.35 MA with ECH+NBI Need P CD = 75 MW P to sustain β N = 172 MW Central Temperature (kev) P INPUT (MW) Density (10 19 m -3 ) (f G = 0.42) Time (s) P CD (MW)

50 With Present Confinement And n e, The SN Hybrid Is Consistent With an ITER 9 MA Scenario INPUTS: R=6.2 m, B t = 5.3 T q 95 =6.2, ε=3.1 β N =3, n lin.av =3.2 SN 9 MA ITER hybrid Plasma current (MA) scaled Impose I p = 9 MA Fix ν* H 98y2 =1.49 Density (10 19 m -3 ) n G (f G = 1.17) SCALED SCENARIO: With n/n G = 1.17 Drive 4.5 MA with ECH+NBI Need P CD = 191 MW P to sustain β N à 175 MW Q = 7.1 Central Temperature (kev) P INPUT (MW) P CD (MW) Time (s)

51 With Present Confinement And lower n e, The SN Hybrid Is Consistent With an ITER 9 MA, Q=4.4 Scenario INPUTS: R=6.2 m, B t = 5.3 T q 95 =6.2, ε=3.1 β N =3, n lin.av =3.2 SN 9 MA ITER hybrid Plasma current (MA) scaled Impose I p = 9 MA Scale f GW H 98y2 =1.49 Density (10 19 m -3 ) n G (f G = 0.9) SCALED SCENARIO: With n/n G = 0.9 Drive 4.5 MA with ECH+NBI Need P CD = 112 MW P to sustain β N à 233 MW Q = 4.4 Central Temperature (kev) P INPUT (MW) P CD (MW) Time (s)

Plasma Stability in Tokamaks and Stellarators

Plasma Stability in Tokamaks and Stellarators Plasma Stability in Tokamaks and Stellarators Gerald A. Navratil GCEP Fusion Energy Workshop Princeton, NJ 1- May 006 ACKNOWLEDGEMENTS Borrowed VGs from many colleagues: J. Bialek, A. Garofalo,R. Goldston,

More information

DIII D Research in Support of ITER

DIII D Research in Support of ITER Research in Support of ITER by E.J. Strait and the Team Presented at 22nd IAEA Fusion Energy Conference Geneva, Switzerland October 13-18, 28 DIII-D Research Has Made Significant Contributions in the Design

More information

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012 Impact of Torque and Rotation in High Fusion Performance Plasmas by W.M. Solomon 1 K.H. Burrell 2, R.J. Buttery 2, J.S.deGrassie 2, E.J. Doyle 3, A.M. Garofalo 2, G.L. Jackson 2, T.C. Luce 2, C.C. Petty

More information

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual

More information

Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod

Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod JUST DID IT. J A Snipes, N Basse, C Boswell, E Edlund, A Fasoli #, N N Gorelenkov, R S Granetz, L Lin, Y Lin, R Parker, M Porkolab, J

More information

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK GA A24738 STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK by T.C. LUCE, C.C. PETTY, D.A. HUMPHREYS, R.J. LA HAYE, and R. PRATER JULY 24 DISCLAIMER This

More information

Supported by. Role of plasma edge in global stability and control*

Supported by. Role of plasma edge in global stability and control* NSTX Supported by College W&M Colorado Sch Mines Columbia U CompX General Atomics INL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U

More information

GA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D

GA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D GA A271 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D by C.C. PETTY, J.S. degrassie, R.W. HARVEY, Y.R. LIN-LIU, J.M. LOHR, T.C. LUCE, M.A. MAKOWSKI, Y.A. OMELCHENKO, and R. PRATER AUGUST 2001 DISCLAIMER This

More information

Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak

Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak M. Garcia-Munoz M. A. Van Zeeland, S. Sharapov, Ph. Lauber, J. Ayllon, I. Classen, G. Conway, J. Ferreira,

More information

Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance

Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance M.Okabayashi, M. Chance, M. Chu* and R. Hatcher A. Garofalo**, R. La Haye*, H. Remeirdes**, T. Scoville*, and T.

More information

Presentation by Herb Berk University of Texas at Austin Institute for Fusion Studies in Vienna, Austria Sept. 1-4, 2015

Presentation by Herb Berk University of Texas at Austin Institute for Fusion Studies in Vienna, Austria Sept. 1-4, 2015 Review of Theory Papers at 14 th IAEA technical meeting on Engertic Particles in Magnetic Confinement systems Presentation by Herb Berk University of Texas at Austin Institute for Fusion Studies in Vienna,

More information

Gyrokinetic Transport Driven by Energetic Particle Modes

Gyrokinetic Transport Driven by Energetic Particle Modes Gyrokinetic Transport Driven by Energetic Particle Modes by Eric Bass (General Atomics) Collaborators: Ron Waltz, Ming Chu GSEP Workshop General Atomics August 10, 2009 Outline I. Background Alfvén (TAE/EPM)

More information

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER by A.M. GAROFALO, K.H. BURRELL, M.J. LANCTOT, H. REIMERDES, W.M. SOLOMON and L. SCHMITZ OCTOBER 2010 DISCLAIMER This report was

More information

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod 1 EX/P4-22 Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod Y. Lin, R.S. Granetz, A.E. Hubbard, M.L. Reinke, J.E.

More information

Rotation and Neoclassical Ripple Transport in ITER

Rotation and Neoclassical Ripple Transport in ITER Rotation and Neoclassical Ripple Transport in ITER Elizabeth J. Paul 1 Matt Landreman 1 Francesca Poli 2 Don Spong 3 Håkan Smith 4 William Dorland 1 1 University of Maryland 2 Princeton Plasma Physics

More information

Energetic particle modes: from bump on tail to tokamak plasmas

Energetic particle modes: from bump on tail to tokamak plasmas Energetic particle modes: from bump on tail to tokamak plasmas M. K. Lilley 1 B. N. Breizman 2, S. E. Sharapov 3, S. D. Pinches 3 1 Physics Department, Imperial College London, London, SW7 2AZ, UK 2 IFS,

More information

PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK

PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK by T.C. LUCE, J.R. FERRON, C.T. HOLCOMB, F. TURCO, P.A. POLITZER, and T.W. PETRIE GA A26981 JANUARY 2011 DISCLAIMER This report was prepared

More information

GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D

GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D by E.J. DOYLE, J.C. DeBOO, T.A. CASPER, J.R. FERRON, R.J. GROEBNER, C.T. HOLCOMB, A.W. HYATT, G.L. JACKSON, R.J. LA HAYE, T.C. LUCE, G.R.

More information

C-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center

C-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center C-Mod Core Transport Program Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center Practical Motivations for Transport Research Overall plasma behavior must be robustly

More information

MHD instability driven by supra-thermal electrons in TJ-II stellarator

MHD instability driven by supra-thermal electrons in TJ-II stellarator MHD instability driven by supra-thermal electrons in TJ-II stellarator K. Nagaoka 1, S. Yamamoto 2, S. Ohshima 2, E. Ascasíbar 3, R. Jiménez-Gómez 3, C. Hidalgo 3, M.A. Pedrosa 3, M. Ochando 3, A.V. Melnikov

More information

Effects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal

Effects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal Effects of stellarator transform on sawtooth oscillations in CTH Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, E.C. Howell, C.A. Johnson, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A.

More information

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations 1 EXC/P5-02 ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations B. Hudson 1, T.E. Evans 2, T.H. Osborne 2, C.C. Petty 2, and P.B. Snyder 2 1 Oak Ridge Institute for Science

More information

The performance of improved H-modes at ASDEX Upgrade and projection to ITER

The performance of improved H-modes at ASDEX Upgrade and projection to ITER EX/1-1 The performance of improved H-modes at ASDEX Upgrade and projection to George Sips MPI für Plasmaphysik, EURATOM-Association, D-85748, Germany G. Tardini 1, C. Forest 2, O. Gruber 1, P. Mc Carthy

More information

Tokamak/Helical Configurations Related to LHD and CHS-qa

Tokamak/Helical Configurations Related to LHD and CHS-qa 9TH WORKSHOP ON MHD STABILITY CONTROL: "CONTROL OF MHD STABILITY: BACK TO THE BASICS" NOVEMBER 21-23, 2004, PRINCETON PLASMA PHYSICS LABORATORY Tokamak/Helical Configurations Related to LHD and CHS-qa

More information

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME by R. NAZIKIAN, M.E. AUSTIN, R.V. BUDNY, M.S. CHU, W.W. HEIDBRINK, M.A. MAKOWSKI, C.C. PETTY, P.A. POLITZER, W.M. SOLOMON, M.A.

More information

Plasma Spectroscopy Inferences from Line Emission

Plasma Spectroscopy Inferences from Line Emission Plasma Spectroscopy Inferences from Line Emission Ø From line λ, can determine element, ionization state, and energy levels involved Ø From line shape, can determine bulk and thermal velocity and often

More information

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS Presented by D.P. SCHISSEL Presented to APS Centennial Meeting March 20 26, 1999 Atlanta, Georgia

More information

Lattice Design and Performance for PEP-X Light Source

Lattice Design and Performance for PEP-X Light Source Lattice Design and Performance for PEP-X Light Source Yuri Nosochkov SLAC National Accelerator Laboratory With contributions by M-H. Wang, Y. Cai, X. Huang, K. Bane 48th ICFA Advanced Beam Dynamics Workshop

More information

Stability Properties of Toroidal Alfvén Modes Driven. N. N. Gorelenkov, S. Bernabei, C. Z. Cheng, K. Hill, R. Nazikian, S. Kaye

Stability Properties of Toroidal Alfvén Modes Driven. N. N. Gorelenkov, S. Bernabei, C. Z. Cheng, K. Hill, R. Nazikian, S. Kaye Stability Properties of Toroidal Alfvén Modes Driven by Fast Particles Λ N. N. Gorelenkov, S. Bernabei, C. Z. Cheng, K. Hill, R. Nazikian, S. Kaye Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton,

More information

DT Fusion Power Production in ELM-free H-modes in JET

DT Fusion Power Production in ELM-free H-modes in JET JET C(98)69 FG Rimini and e JET Team DT Fusion ower roduction in ELM-free H-modes in JET This document is intended for publication in e open literature. It is made available on e understanding at it may

More information

The Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is

The Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is and Stability of Field-Reversed Equilibrium with Toroidal Field Configurations Atomics General Box 85608, San Diego, California 92186-5608 P.O. APS Annual APS Meeting of the Division of Plasma Physics

More information

Minimal Model Study for ELM Control by Supersonic Molecular Beam Injection and Pellet Injection

Minimal Model Study for ELM Control by Supersonic Molecular Beam Injection and Pellet Injection 25 th Fusion Energy Conference, Saint Petersburg, Russia, 2014 TH/P2-9 Minimal Model Study for ELM Control by Supersonic Molecular Beam Injection and Pellet Injection Tongnyeol Rhee 1,2, J.M. Kwon 1, P.H.

More information

Analytical Study of RWM Feedback Stabilisation with Application to ITER

Analytical Study of RWM Feedback Stabilisation with Application to ITER CT/P- Analytical Study of RWM Feedback Stabilisation with Application to ITER Y Gribov ), VD Pustovitov ) ) ITER International Team, ITER Naka Joint Work Site, Japan ) Nuclear Fusion Institute, Russian

More information

GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D

GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D by C.C. PETTY, P.A. POLITZER, R.J. JAYAKUMAR, T.C. LUCE, M.R. WADE, M.E. AUSTIN, D.P. BRENNAN, T.A. CASPER, M.S. CHU, J.C. DeBOO, E.J. DOYLE,

More information

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison Heat Transport in a Stochastic Magnetic Field John Sarff Physics Dept, UW-Madison CMPD & CMSO Winter School UCLA Jan 5-10, 2009 Magnetic perturbations can destroy the nested-surface topology desired for

More information

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE T.H. Osborne 1, P.B. Snyder 1, R.J. Groebner 1, A.W. Leonard 1, M.E. Fenstermacher 2, and the DIII-D Group 47 th Annual Meeting

More information

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant

More information

QTYUIOP ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. Presented by. for the DIII D Team*

QTYUIOP ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. Presented by. for the DIII D Team* ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR Presented by D.P. SCHISSEL for the DIII D Team* Presented to 38th APS/DPP Meeting NOVEMBER 11 15, 1996 Denver, Colorado

More information

Saturated ideal modes in advanced tokamak regimes in MAST

Saturated ideal modes in advanced tokamak regimes in MAST Saturated ideal modes in advanced tokamak regimes in MAST IT Chapman 1, M-D Hua 1,2, SD Pinches 1, RJ Akers 1, AR Field 1, JP Graves 3, RJ Hastie 1, CA Michael 1 and the MAST Team 1 EURATOM/CCFE Fusion

More information

Variation of Turbulence and Transport with the Te/Ti Ratio in H-Mode Plasmas

Variation of Turbulence and Transport with the Te/Ti Ratio in H-Mode Plasmas Variation of Turbulence and Transport with the Te/Ti Ratio in H-Mode Plasmas by G.R. McKee with C.H. Holland, C.C. Petty, H. Reimerdes,5, T.R. Rhodes6,L. Schmitz6, S. Smith, I.U. Uzun-Kaymak, G. Wang6,

More information

arxiv:physics/ v1 [physics.plasm-ph] 5 Nov 2004

arxiv:physics/ v1 [physics.plasm-ph] 5 Nov 2004 Ion Resonance Instability in the ELTRAP electron plasma G. Bettega, 1 F. Cavaliere, 2 M. Cavenago, 3 A. Illiberi, 1 R. Pozzoli, 1 and M. Romé 1 1 INFM Milano Università, INFN Sezione di Milano, Dipartimento

More information

Comparison of Kinetic and Extended MHD Models for the Ion Temperature Gradient Instability in Slab Geometry

Comparison of Kinetic and Extended MHD Models for the Ion Temperature Gradient Instability in Slab Geometry Comparison of Kinetic and Extended MHD Models for the Ion Temperature Gradient Instability in Slab Geometry D. D. Schnack University of Wisconsin Madison Jianhua Cheng, S. E. Parker University of Colorado

More information

Introduction to Fusion Physics

Introduction to Fusion Physics Introduction to Fusion Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 Energy from nuclear fusion Reduction

More information

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO 21 st IAEA Fusion Energy Conference Chengdu, China Oct. 16-21, 2006 DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO R. Maingi 1, A. Kirk 2, T. Osborne 3, P. Snyder 3, S. Saarelma 2, R. Scannell

More information

Overview of Pilot Plant Studies

Overview of Pilot Plant Studies Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology

More information

Neoclassical Tearing Modes

Neoclassical Tearing Modes Neoclassical Tearing Modes O. Sauter 1, H. Zohm 2 1 CRPP-EPFL, Lausanne, Switzerland 2 Max-Planck-Institut für Plasmaphysik, Garching, Germany Physics of ITER DPG Advanced Physics School 22-26 Sept, 2014,

More information

Approach to Steady-state High Performance in DD and DT with Optimised Shear on JET

Approach to Steady-state High Performance in DD and DT with Optimised Shear on JET JET P(98) F X Söldner et al Approach to Steady-state High Performance in DD and DT with Optimised Shear on JET This document is intended for publication in the open literature. It is made available on

More information

GA A23736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT

GA A23736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT GA A3736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT by T.C. LUCE, C.C. PETTY, and J.E. KINSEY AUGUST DISCLAIMER This report was prepared as an account of work sponsored by an

More information

arxiv: v1 [physics.plasm-ph] 11 Mar 2016

arxiv: v1 [physics.plasm-ph] 11 Mar 2016 1 Effect of magnetic perturbations on the 3D MHD self-organization of shaped tokamak plasmas arxiv:1603.03572v1 [physics.plasm-ph] 11 Mar 2016 D. Bonfiglio 1, S. Cappello 1, M. Veranda 1, L. Chacón 2 and

More information

2/8/16 Dispersive Media, Lecture 5 - Thomas Johnson 1. Waves in plasmas. T. Johnson

2/8/16 Dispersive Media, Lecture 5 - Thomas Johnson 1. Waves in plasmas. T. Johnson 2/8/16 Dispersive Media, Lecture 5 - Thomas Johnson 1 Waves in plasmas T. Johnson Introduction to plasma physics Magneto-Hydro Dynamics, MHD Plasmas without magnetic fields Cold plasmas Transverse waves

More information

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén Current density modelling in JET and JT-60U identity plasma experiments Paula Sirén 1/12 1/16 Euratom-TEKES Euratom-Tekes Annual Seminar 2013 28 24 May 2013 Paula Sirén Current density modelling in JET

More information

Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment

Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment 1 EXS/P2-07 Nonsolenoidal Startup and Plasma Stability at Near-Unity Aspect Ratio in the Pegasus Toroidal Experiment R.J. Fonck 1), D.J. Battaglia 2), M.W. Bongard 1), E.T. Hinson 1), A.J. Redd 1), D.J.

More information

ITER PHYSICS BASIS CHAPTER 5 PHYSICS OF ENERGETIC IONS TABLE OF CONTENTS

ITER PHYSICS BASIS CHAPTER 5 PHYSICS OF ENERGETIC IONS TABLE OF CONTENTS ITER PHYSICS BASIS CHAPTER 5 PHYSICS OF ENERGETIC IONS TABLE OF CONTENTS CHAPTER 5: PHYSICS OF ENERGETIC IONS...1 5.1. INTRODUCTION...2 5.2. CLASSICAL PHYSICS OF ENERGETIC PARTICLE CONFINEMENT AND PLASMA

More information

q(0) pressure after crash 1.0 Single tearing on q=2 Double tearing on q=2 0.5

q(0) pressure after crash 1.0 Single tearing on q=2 Double tearing on q=2 0.5 EX/P-1 MHD issues in Tore Supra steady-state fully non-inductive scenario P Maget 1), F Imbeaux 1), G Giruzzi 1), V S Udintsev ), G T A Huysmans 1), H Lütjens 3), J-L Ségui 1), M Goniche 1), Ph Moreau

More information

Macroscopic Stability of High β N MAST Plasmas

Macroscopic Stability of High β N MAST Plasmas 1 EXS/P5-4 Macroscopic Stability of High β N MAST Plasmas I.T. Chapman 1), R.J. Akers 1), L.C. Appel 1), N.C. Barratt 2), M.F. de Bock 1,7), A.R. Field 1), K.J. Gibson 2), M.P. Gryaznevich 1), R.J. Hastie

More information

Impact of Energetic-Ion-Driven Global Modes on Toroidal Plasma Confinements

Impact of Energetic-Ion-Driven Global Modes on Toroidal Plasma Confinements Impact of Energetic-Ion-Driven Global Modes on Toroidal Plasma Confinements Kazuo TOI CHS & LHD Experimental Group National Institute for Fusion Science Toki 59-5292, Japan Special contributions from:

More information

Beams and magnetized plasmas

Beams and magnetized plasmas Beams and magnetized plasmas 1 Jean-Pierre BOEUF LAboratoire PLAsma et Conversion d Energie LAPLACE/ CNRS, Université Paul SABATIER, TOULOUSE Beams and magnetized plasmas 2 Outline Ion acceleration and

More information

Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX

Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1, D.L. Brower 2, C. Deng 2, D.T.Anderson 1, F.S.B. Anderson 1, A.F. Almagri

More information

Evaluation of CT injection to RFP for performance improvement and reconnection studies

Evaluation of CT injection to RFP for performance improvement and reconnection studies Evaluation of CT injection to RFP for performance improvement and reconnection studies S. Masamune A. Sanpei, T. Nagano, S. Nakanobo, R. Tsuboi, S. Kunita, M. Emori, H. Makizawa, H. Himura, N. Mizuguchi

More information

MST and the Reversed Field Pinch. John Sarff

MST and the Reversed Field Pinch. John Sarff MST and the Reversed Field Pinch John Sarff APAM Columbia University Sep 19, 2014 Outline Tutorial-level review of tearing stability, magnetic relaxation, and transport in the RFP Ion-related physics topics

More information

arxiv: v2 [physics.plasm-ph] 24 Jul 2017

arxiv: v2 [physics.plasm-ph] 24 Jul 2017 Rotation and Neoclassical Ripple Transport in ITER E. J. Paul Department of Physics, University of Maryland, College Park, MD 20742, USA arxiv:1703.06129v2 [physics.plasm-ph] 24 Jul 2017 M. Landreman Institute

More information

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions P.B. Snyder 1, T.H. Osborne 1, M.N.A. Beurskens 2, K.H. Burrell 1, R.J. Groebner 1, J.W. Hughes 3, R. Maingi

More information

A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva

A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva CRPP - EPFL SPS Annual Meeting 2014 02.07.2014 CRPP The tokamak

More information

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport 1 Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama Japan Atomic Energy Agency, Naka, Ibaraki-ken, 311-0193 Japan

More information

MODELING AND SIMULATION OF LOW TEMPERATURE PLASMA DISCHARGES

MODELING AND SIMULATION OF LOW TEMPERATURE PLASMA DISCHARGES MODELING AND SIMULATION OF LOW TEMPERATURE PLASMA DISCHARGES Michael A. Lieberman University of California, Berkeley lieber@eecs.berkeley.edu DOE Center on Annual Meeting May 2015 Download this talk: http://www.eecs.berkeley.edu/~lieber

More information

Dimensionless Identity Experiments in JT-60U and JET

Dimensionless Identity Experiments in JT-60U and JET 1 IAEA-CN-116/IT/1-2 Dimensionless Identity Experiments in JT-60U and JET G Saibene 1, N Oyama 2, Y Andrew 3, JG Cordey 3, E de la Luna 4, C Giroud 3, K Guenther 3, T Hatae 2, GTA Huysmans 5, Y Kamada

More information

Research of Basic Plasma Physics Toward Nuclear Fusion in LHD

Research of Basic Plasma Physics Toward Nuclear Fusion in LHD Research of Basic Plasma Physics Toward Nuclear Fusion in LHD Akio KOMORI and LHD experiment group National Institute for Fusion Science, Toki, Gifu 509-5292, Japan (Received 4 January 2010 / Accepted

More information

The RFP: Plasma Confinement with a Reversed Twist

The RFP: Plasma Confinement with a Reversed Twist The RFP: Plasma Confinement with a Reversed Twist JOHN SARFF Department of Physics University of Wisconsin-Madison Invited Tutorial 1997 Meeting APS DPP Pittsburgh Nov. 19, 1997 A tutorial on the Reversed

More information

ELM control with RMP: plasma response models and the role of edge peeling response

ELM control with RMP: plasma response models and the role of edge peeling response ELM control with RMP: plasma response models and the role of edge peeling response Yueqiang Liu 1,2,3,*, C.J. Ham 1, A. Kirk 1, Li Li 4,5,6, A. Loarte 7, D.A. Ryan 8,1, Youwen Sun 9, W. Suttrop 10, Xu

More information

Phase ramping and modulation of reflectometer signals

Phase ramping and modulation of reflectometer signals 4th Intl. Reflectometry Workshop - IRW4, Cadarache, March 22nd - 24th 1999 1 Phase ramping and modulation of reflectometer signals G.D.Conway, D.V.Bartlett, P.E.Stott JET Joint Undertaking, Abingdon, Oxon,

More information

International Workshop on the Frontiers of Modern Plasma Physics July On the Nature of Plasma Core Turbulence.

International Workshop on the Frontiers of Modern Plasma Physics July On the Nature of Plasma Core Turbulence. 1953-43 International Workshop on the Frontiers of Modern Plasma Physics 14-25 July 2008 On the Nature of Plasma Core Turbulence. F. Jenko Max-Planck Institute fuer Plasmaphysik Garching bei Munchen Germany

More information

Investigations of pedestal turbulence and ELM bursts in NSTX H-mode plasmas

Investigations of pedestal turbulence and ELM bursts in NSTX H-mode plasmas Supported by Investigations of pedestal turbulence and ELM bursts in NSTX H-mode plasmas Coll of Wm & Mary Columbia U CompX General Atomics FIU INL Johns Hopkins U LANL LLNL Lodestar MIT Lehigh U Nova

More information

Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain

Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain arxiv:146.5245v1 [physics.plasm-ph] 2 Jun 214 D. P. Brennan and J. M. Finn June 23, 214 Department of Astrophysical

More information

Toroidal confinement of non-neutral plasma. Martin Droba

Toroidal confinement of non-neutral plasma. Martin Droba Toroidal confinement of non-neutral plasma Martin Droba Contents Experiments with toroidal non-neutral plasma Magnetic surfaces CNT and IAP-high current ring Conclusion 2. Experiments with toroidal non-neutral

More information

Significance of MHD Effects in Stellarator Confinement

Significance of MHD Effects in Stellarator Confinement Significance of MHD Effects in Stellarator Confinement A. Weller 1, S. Sakakibara 2, K.Y. Watanabe 2, K. Toi 2, J. Geiger 1, M.C. Zarnstorff 3, S.R. Hudson 3, A. Reiman 3, A. Werner 1, C. Nührenberg 1,

More information

Relativistic magnetotransport in graphene

Relativistic magnetotransport in graphene Relativistic magnetotransport in graphene Markus Müller in collaboration with Lars Fritz (Harvard) Subir Sachdev (Harvard) Jörg Schmalian (Iowa) Landau Memorial Conference June 6, 008 Outline Relativistic

More information

Introduction to Relaxation Theory James Keeler

Introduction to Relaxation Theory James Keeler EUROMAR Zürich, 24 Introduction to Relaxation Theory James Keeler University of Cambridge Department of Chemistry What is relaxation? Why might it be interesting? relaxation is the process which drives

More information

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a)

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a) 1 TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a) 1 Chang, C.S., 1 Ku, S., 2 Adams M., 3 D Azevedo, G., 4 Chen, Y., 5 Cummings,

More information

DEMONSTRATION IN THE DIII-D TOKAMAK OF AN ALTERNATE BASELINE SCENARIO FOR ITER AND OTHER BURNING PLASMA EXPERIMENTS

DEMONSTRATION IN THE DIII-D TOKAMAK OF AN ALTERNATE BASELINE SCENARIO FOR ITER AND OTHER BURNING PLASMA EXPERIMENTS GA-A24145 DEMONSTRATION IN THE DIII-D TOKAMAK OF AN ALTERNATE BASELINE SCENARIO FOR ITER AND OTHER BURNING PLASMA EXPERIMENTS by TC LUCE, MR WADE, JR FERRON, AW HYATT, AG KELLMAN, JE KINSEY, RJ LA HAYE,

More information

Nuclear spin maser with a novel masing mechanism and its application to the search for an atomic EDM in 129 Xe

Nuclear spin maser with a novel masing mechanism and its application to the search for an atomic EDM in 129 Xe Nuclear spin maser with a novel masing mechanism and its application to the search for an atomic EDM in 129 Xe A. Yoshimi RIKEN K. Asahi, S. Emori, M. Tsukui, RIKEN, Tokyo Institute of Technology Nuclear

More information

Damping of MHD waves in the solar partially ionized plasmas

Damping of MHD waves in the solar partially ionized plasmas Damping of MHD waves in the solar partially ionized plasmas M. L. Khodachenko Space Research Institute, Austrian Academy of Sciences, Graz, Austria MHD waves on the Sun Magnetic field plays the key role

More information

PFC/JA NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT

PFC/JA NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT PFC/JA-88-12 NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT J. Wei, L. Bromberg, R. C. Myer, and D. R. Cohn Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts 2139 To

More information

Fast Secondary Reconnection and the Sawtooth Crash

Fast Secondary Reconnection and the Sawtooth Crash Fast Secondary Reconnection and the Sawtooth Crash Maurizio Ottaviani 1, Daniele Del Sarto 2 1 CEA-IRFM, Saint-Paul-lez-Durance (France) 2 Université de Lorraine, Institut Jean Lamour UMR-CNRS 7198, Nancy

More information

CHAPTER 8 PERFORMANCE-LIMITING MAGNETOHYDRODYNAMICS IN JET

CHAPTER 8 PERFORMANCE-LIMITING MAGNETOHYDRODYNAMICS IN JET CHAPTER 8 PERFORMANCE-LIMITING MAGNETOHYDRODYNAMICS IN JET R. J. BUTTERY* and T. C. HENDER EURATOM0UKAEA Fusion Association, Culham Science Centre Abingdon, Oxfordshire OX14 3DB, United Kingdom Received

More information

HFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION

HFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION ASDEX Upgrade Session: "Issues and prospects of effcient fueling for magnetic confinement" HFS ELLET REFUELING FOR HIGH DENSITY TOKAMAK OERATION.T. Lang for the ASDEX Upgrade and JET teams Cubic mm size

More information

Introduction. Resonant Cooling of Nuclear Spins in Quantum Dots

Introduction. Resonant Cooling of Nuclear Spins in Quantum Dots Introduction Resonant Cooling of Nuclear Spins in Quantum Dots Mark Rudner Massachusetts Institute of Technology For related details see: M. S. Rudner and L. S. Levitov, Phys. Rev. Lett. 99, 036602 (2007);

More information

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model 1 THC/3-3 ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model J.E. Kinsey, G.M. Staebler, J. Candy, and R.E. Waltz General Atomics, P.O. Box 8608, San Diego, California

More information

Impact of neutral atoms on plasma turbulence in the tokamak edge region

Impact of neutral atoms on plasma turbulence in the tokamak edge region Impact of neutral atoms on plasma turbulence in the tokamak edge region C. Wersal P. Ricci, F.D. Halpern, R. Jorge, J. Morales, P. Paruta, F. Riva Theory of Fusion Plasmas Joint Varenna-Lausanne International

More information

High-power ECH and fully non-inductive operation with ECCD in the TCV tokamak

High-power ECH and fully non-inductive operation with ECCD in the TCV tokamak Plasma Phys. Control. Fusion 42 (2000) B311 B321. Printed in the UK PII: S0741-3335(00)17239-2 High-power ECH and fully non-inductive operation with ECCD in the TCV tokamak S Coda, T P Goodman, M A Henderson,

More information

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations. Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations. M. Becoulet 1, F. Orain 1, G.T.A. Huijsmans 2, P. Maget 1, N. Mellet 1, G. Dif-Pradalier 1, G. Latu 1, C. Passeron

More information

On Electron-Cyclotron Waves in Relativistic Non-Thermal Tokamak Plasmas

On Electron-Cyclotron Waves in Relativistic Non-Thermal Tokamak Plasmas 1 On Electron-Cyclotron Waves in Relativistic Non-Thermal Tokamak Plasmas Lj. Nikolić and M.M. Škorić Vinča Institute of Nuclear Sciences, P.O.Box 522, Belgrade 11001, Serbia and Montenegro ljnikoli@tesla.rcub.bg.ac.yu

More information

GA A27849 APPLICATION OF ELECTRON CYCLOTRON HEATING TO THE STUDY OF TRANSPORT IN ITER BASELINE SCENARIO-LIKE DISCHARGES IN DIII-D

GA A27849 APPLICATION OF ELECTRON CYCLOTRON HEATING TO THE STUDY OF TRANSPORT IN ITER BASELINE SCENARIO-LIKE DISCHARGES IN DIII-D GA A27849 APPLICATION OF ELECTRON CYCLOTRON HEATING TO THE STUDY OF TRANSPORT IN ITER BASELINE by R.I. PINSKER, M.E. AUSTIN, D.R. ERNST, A.M. GAROFALO, B.A. GRIERSON, J.C. HOSEA, T.C. LUCE, A. MARINONI,

More information

Effect of local E B flow shear on the stability of magnetic islands in tokamak plasmas

Effect of local E B flow shear on the stability of magnetic islands in tokamak plasmas Effect of local E B flow shear on the stability of magnetic islands in tokamak plasmas R. Fitzpatrick and F. L. Waelbroeck Citation: Physics of Plasmas (1994-present) 16, 052502 (2009); doi: 10.1063/1.3126964

More information

TRANSP Simulations of ITER Plasmas

TRANSP Simulations of ITER Plasmas PPPL-3152 - Preprint Date: December 1995, UC-420, 421, 427 TRANSP Simulations of ITER Plasmas R. V. Budny, D. C. McCune, M. H. Redi, J. Schivell, and R. M. Wieland Princeton University Plasma Physics Laboratory

More information

Production of Over-dense Plasmas by Launching. 2.45GHz Electron Cyclotron Waves in a Helical Device

Production of Over-dense Plasmas by Launching. 2.45GHz Electron Cyclotron Waves in a Helical Device Production of Over-dense Plasmas by Launching 2.45GHz Electron Cyclotron Waves in a Helical Device R. Ikeda a, M. Takeuchi a, T. Ito a, K. Toi b, C. Suzuki b, G. Matsunaga c, S. Okamura b, and CHS Group

More information

Verification & Validation: application to the TORPEX basic plasma physics experiment

Verification & Validation: application to the TORPEX basic plasma physics experiment Verification & Validation: application to the TORPEX basic plasma physics experiment Paolo Ricci F. Avino, A. Bovet, A. Fasoli, I. Furno, S. Jolliet, F. Halpern, J. Loizu, A. Mosetto, F. Riva, C. Theiler,

More information

Multimachine Extrapolation of Neoclassical Tearing Mode Physics to ITER

Multimachine Extrapolation of Neoclassical Tearing Mode Physics to ITER 1 IT/P6-8 Multimachine Extrapolation of Neoclassical Tearing Mode Physics to ITER R. J. Buttery 1), S. Gerhardt ), A. Isayama 3), R. J. La Haye 4), E. J. Strait 4), D. P. Brennan 5), P. Buratti 6), D.

More information

Co-existence and interference of multiple modes in plasma turbulence: Some recent GENE results

Co-existence and interference of multiple modes in plasma turbulence: Some recent GENE results Co-existence and interference of multiple modes in plasma turbulence: Some recent GENE results Frank Jenko IPP Garching, Germany University of Ulm, Germany Acknowledgements: F. Merz, T. Görler, D. Told,

More information

Penning Traps. Contents. Plasma Physics Penning Traps AJW August 16, Introduction. Clasical picture. Radiation Damping.

Penning Traps. Contents. Plasma Physics Penning Traps AJW August 16, Introduction. Clasical picture. Radiation Damping. Penning Traps Contents Introduction Clasical picture Radiation Damping Number density B and E fields used to increase time that an electron remains within a discharge: Penning, 936. Can now trap a particle

More information

GA A27433 THE EPED PEDESTAL MODEL: EXTENSIONS, APPLICATION TO ELM-SUPPRESSED REGIMES, AND ITER PREDICTIONS

GA A27433 THE EPED PEDESTAL MODEL: EXTENSIONS, APPLICATION TO ELM-SUPPRESSED REGIMES, AND ITER PREDICTIONS GA A27433 THE EPED PEDESTAL MODEL: EXTENSIONS, APPLICATION TO ELM-SUPPRESSED REGIMES, AND ITER PREDICTIONS by P.B. SNYDER, T.H. OSBORNE, M.N.A. BEURSKENS, K.H. BURRELL, R.J. GROEBNER, J.W. HUGHES, R. MAINGI,

More information